ML19305D147
| ML19305D147 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/19/1980 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML19305D145 | List: |
| References | |
| NUDOCS 8004140101 | |
| Download: ML19305D147 (32) | |
Text
{{#Wiki_filter:- . -. .. - _. - AGENDA FOR PRESENTATION TO Ti!E USNRC l RECARDING PRAIRIE ISLAND FUEL POOL MODIFICATION MARCII 19, 1980 , PillLLIPS BUILDING - ROOM Pt 10 I. INTRODUCTION (NSP) - 15 MINUTES j A. NEED FOR MODIFICATION f B. GENERAL DESCRIPTION OF MODIFICATION C. SCllEl)ULE i I i II. TECHNICAL DESCRIPTION OF MODIFICATION AND l COMPARISON WITil GTilER PLANTS (NSC) - 2 Il0URS i i A. MATERIALS [
- l. 304 and 17-4 Pil STAINLESS STEEL [
i i-i
- 2. BORAFl.EX !
t B. NUCLEAR ANALYSIS ! C. RACK STRUCTURAL ANALYSIS D. TilERMAL ANALYSIS . E. RADIO CllEMICAL ANALYSIS [ F. BUILDING STRUCTURAL ANALYSIS ! i III. INSTALLATION (NSC/NSP) - 10 MINUTES IV.
SUMMARY
(NSP) - 10 MINUTES l i. t t 9 i 800434gg,, 8
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PRA!RIE l'.AMD SPEt4T FUEL STORAGE HI5704tCAL CATA AND F08ECAsi PoESENT SPENT k"UEL ST0oAGE 4EcANGEME?T TOTAL TOTAL NO.(6) i CF TOTAL I0} REFUEL!nc UNIT !! UNIT ! 70 REMAINING SP4CES 04TE ASSEMBLtES A55E99L!ES 04?E S7 ACES OCCuplEO 1980 40 40 360 327 52 1981 40 41(I) 44f(2) 245 64 1982 41(l) 40 522(3)(4) 165 76 1983 40 40 602 85 87 Full Core Storsge for 121 Assemblies is no Longer Availaole 1984 40 40 682 5 99 PoGPCSED SPENT FUEL ST02 AGE M00!FICAT!CH (to be complete in late 1981) 1982 40 40 522 357 38 1783 40 40 602 177 44 1984 40 40 682 697 49 1985 40 40 762 617 55 , 1?86 40 40 842 537 51
!?87 40 40 922 457 67 li?8 40 40 1C02 377 73 O 1989 40 40 1082{5) 297 78 1770 40 40 1162 217 84 1991 40 40 1242 137 90 1992 40 40 1322 57 96 1993 40(I) 4C 1402 100
.CTE S (1) Exxon delivers 201 fuel assemol f es for each unit on their 5-year c:ntract.
(2) Natimum contemslated capacity of pool 1 with nign density spent fuel storage racks - 462 assemolles. The Todification can be made during Su vrer and Fall 1981 with all fuel stored in Pool 1. (3) Pool 2 cacact ty - 555 assevoltes. (4) The next refueling discharge will require storsge of scent fuel in Pool 1. Presently our Itcense does not allow handling nesvy ocjects above a pool storing irradiated fuel. Pool 1 is in the crane movenent pathway and also is required for shipping spent fuel. (5) 8 col 2 modified capacity - 1120 assemolies.
. Crane modification required to move heavy loads over Pool 1 after next refueling. (See Note 4) f ci) Pool 1 and 2 total mdtfied capacity - 1582 assemblies. However, four modules avst be remved from Pool 1 for scent fuel sht:af ng cask handling. There fore, only 1379 storage locations are swallaole for rormi storage.
(7) Af ter the first refueling in 1993, normal storage capacity 4111 be ennausted. egp go$@ l
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TRANSFER CANAL , i l I ! 7X8 7X8 7X8 , 7X8 i 7X7 7X7 7X7 7X7 i--___,. 4 l_7X8_ ____f: . 7 X 8 r ,i NEW FUEL PIT 7X7 7X8 7X8 7X8 7X8 i 7X8 7X8 7X8 L - l I ! 7X7l 7X8 7/8 7X8 7X7 7X7 7X7 7X7 i l _ _ _ .1 3 E, Y POOL 1 P0OL 2 L Four 7X7 Racks or Shipping Cask 1386 STORAGE SPACES FIGilRE 3 FINAI. STORAGE CONFIGURATION ,
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i SCHEDULE -- NRC License Amendment Request January 1980 Requested NRC Amendment September 1980 start of Installation Ma::ch 1981 Complete Installation January 1982
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'? Schedule - MEA /MEQB i i MEA Certificate of Need Application September 1979 MEA Application Accepted November 1979 l MEA Prehearing Conferences January / February 1980 t-MEA Hearings ???
- Request MEQB for EIS February 1980 MEQB Prehearing Conferences April 1980 MEQB Hearing May 1980? )
l
ISSUES
- 1. State jurisdiction
- 2. Health testimony
- 3. Safety testimony
- 4. Environmental Impact Statement ACTION
- l. NRC Environment Impact Appraisal
- 2. NRC Safety Evaluation Report
- 3. NRC License Amendment
- 4. Install all racks (administrative limit) 4 v - - + - - - , , , .
t PRAIRIE PRAIRIE NINE MILE POINT ISLAND ISLAND POINT BEACl! 1980 1976 UNIT 1 MODIFICATION Reactor Type PWR PWR BWR PWR Fuel Type Westinghouse Westinghouse General Westinghouse 14 x 14 14 x 14 Electric 14 x 14 Storage Rack 9.5" x 9.5" 13.3" x 13.3" 9.3" x 5.9" 12.43" x 8.43" Pitch I L e I
. . _ _ _ _ , . - . . . . . . _. -- ,. _ , , ,_ . . . . _ _ _ . _ _ _ - . _ _ ._ - . ~ .
I PRAIRIE ISLAND 1980 PRAIRIE ISLAND 1976 NINE MILE POINT POINT BEACH Boraflex None Boraflex Boraflex Neutron Absorber 304 Stainless steel 304 Stainless steel 304 Stainless steel Rack 304 Stainless steel Material 17-4Ph Stainless 17-4Ph Stainless steel (leg adjusting steel (leg adjusting bolts) bolts)
I PRAIRIE ISLAND 1980 PRAIRIE NINE POINT ISLAND MILE BEACli 1976 POINT W NUCLEAR ANALYSIS W Exxon (Optimized) 0.900 0.902 0.934 0.867 0.878 0.890 Nominal keff 0.908 0.910 0.942 0.890 0.897 0.904 Maximum keff 8 1
.. ., .,n. , . . . , . - ...
j PRAIRIE NINE MILE POINT PRAIRIE BEACH ISLAND ISLAND POINT 1980 1976 PDQ-7 LEOPARD Computer Codes XSDRN CHEETAH-P/PDO-7 KENO-IV/AMPX LEOPARD PDQ-7 CHEETAH NITAWL/AMPX MUFT KENO-IV CITATION KENO-IV SOFOCATE NITAWL/AMPX LEOPARD /PDQ-7
I PRAIRIE ISLAND PRAIRIE ISLAND NINE MILE POINT POINT BEACll 1980 MODIFICATION 1976 UNIT 1
- 1. 399/cm U 235 2. 38.979/cm U235 1. 3.0 w/o U235 1. 4.0 w/o U235
- 2. Infinite Array 2. Unborated water 2. Fresh, nondepleted 2. Infinite array fue1
- 3. Clean, unborated 3. Minor structural 3. No burnable poison 3. No burnable poison water members replaced by water
- 4. No credit for -
- 4. Presh, nondepleted rack structure ; fuel
- 5. No absorption 5. Burnable poison fuel grid and control rods replaced by water holes
- 6. Axial leakage included
- 7. Fresh, nondepleted fuel
- 8. Boron-10 density is 0.04 9/cm2 ,
- 9. No burnable poison
I NINE MILE PRAIRIE ISLAND 1980 PRAIRIE ISLAND 1976 POINT POINT BEACil STRUCTURAL ANALYSIS Load Load Load Load Load Combinations Combinations Limits Combinations Limits Combinations Combinations Limits-D+B..............S D+L......... Normal limits D, L, E, E', D+L.............S D+B+E............S D+L+E....... Normal limits D+L+E...........S D+B+Q............l.5S D+L+To......l.5 times normal D+L+T o +R o +E'....l.6/S (To&Ro=0) D+B+Q+E......... 1.5S D+L+T o +E....l.5 times normal D+B+E'...........l.6S D+L+Ta+E....l.6 times normal D+B+E'+Q.........l.6S D+L+T a +E'.. 2.0 times normal D+B+U............(4) D+B+M............(4) and T e TO negligibie.ffects are
t PRAIRIE ISLAND PRAIRIE ISLAND NINE MILE POINT POINT BEACil 1980 1976 Stress USNRC Standard Re- AISC 1969, 7th USNRC Standard Re- USNRC Standard Re-Limits view Plan 3.8.4 Edition view Plan 3.8.4 view Plan, Section Used 3.8.4 ASME Boiler and ACI 318-63 ASME BPVC VIII, ASME BPVC Pressure Vessel Div. 1 Code III, Sub-section NA, App. I AISC FSAR Vol. 5, AISC 1970, 7 th AISC 7th Edition Appendix B Edition ACI 318-63 E e _ . _ _ _ _ _ _ _ . _ . _ _ .__ . . _. . _ , _ - _ _ _m -
PRAIRIE ISLAND 1980 NINE MILE POINT POINT DEACil PRAIRIE ISLAND [976
- 1. Seismic analysis 1. Respo'nse spectrum 1. Seismic analysis Analysis 1. Sliding analysis utilizing spectrum Methods used to determine based on standard analysis was per-response curves.
maximum displace- equations of mo- formed in accor-ment under SSE. Lion for damped dance with FSAR Non linear time linear systems (Reference 3). histroy analysis used to find the using ANSYS code lowest natural used. frequencies, and the response spectrum analysis.
- 2. Seismic accelera- 2. Natural frequencies
- 2. Seismic analysis 2. Static load calculated using using finite analysis using tions computed by-SRSS method. CTAC code, (finite element mathemat- finite element ical model. model. element model) .
- 3. Static and 3. Lateral natural 3. The stress resul-
- 3. Thermal stress tant was calcu-analysis using dynamic analysis frequencies cal-lated by SRSS.
finite element using finite culated using model. element model. finito element
- ANSYS Code.
- 4. Fuel assembly 4. Fuel assembly 4. Reactivity effect
- 4. Grapple load was evaluated computed by drop analysis drop analysis from a height and ruptured fuel using the N-S 1940 elastic analy-of 12". pin analysis in El Centro time sis. history motions.
accordance with FSAR Appen. E.
- 5. Accident analysis 5. Cask anti-tip S. Fuel bundle frame. analysis.
drop analysis assumptions from using energy FSAR, Appendix E. balance methods, and elasto-l plastic analysis, from a height l of 18".
- 6. Overturning /
Stability analysis.
I PRAIRIE PRAIRIE NINE ISLAND ISLAND MILE 1980 1976 POINT POINT BEACH TIIERMAL ANALYSIS Fuel pool max. Base Revised temperature for: Plan Plan Normal Refuel 124*F 140*F 128*F 125'F 120*F Full-core Discharge 141*F 143*F 140*F 125'F 120*F Methods Used POOLI.7, CIRCUS Codes USNRC Standard Re- ANS-5.1 USNRC Standard Review used in accordance view Plan, 9.2.5. ANS 18.6 Plan, 9.2.5 with USNRC SRP 9.2.5 and Branch Technical Position APCSB 9-2. a
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT . SPENT FUEL POOL STRUCTURAL EVALUATION A. Introduction e Original design performed by Pioneer Service ' and Engineering Co. e Flour-Pioneer, Inc. performed re-evaluation for increased rack loads for 1976 modifications (existing racks) e Proposed modifications would use free-standing racks and so would have no rack loads on walls s Pool floor, canal wall, and the walls and columns supporting the pool floor re-evaluated using increased loads from proposed high density racks , 1 l l i t i
I B. Load Combinations, Evaluation Methods and Criteria e Pertinent load combinations and evaluation criteria are shown in the table and are in accordance with USNRC Standard Review Plan 3.8.4. e Pool floor and canal wall were evaluated using the maximum loads from both full and empty canal conditions. e Where applicable existing stresses from loads other than from high density racks were taken from earlier (1977) safety evaluation report by Flour-Pioneer, Inc. e ACI 318-77 code was used. e Elastic analysis were performed using both finite element (stardyne code) and conventional hand computation methods.
TABLE LOAD COMBINATION AND EVALUATION CRITERIA Loading Design Pertinent Load Combination Used (1) Loading (2) Condition Method Limit 1 Service Working 0+H S Stress 0+H+E S Ul timate 1.4 0't 1.4 H U Strength 1.4 0 + 1.4 H + 1.9 E U (1.4 0 + 1.4 H + 1.7 T, + 1.9 E) 0.75 U Factored Ul timate 0+H+T +0 E' U Strength 0+H+T, U 0+H+T +a 1.25 E U 0 + H + T, + E' U , (1) For definitions of symbois, see Section 3.1. (2) S is the required section strength based on the working stress design , method and the allowable stresses defined in ACI-318-77. ; U is the section strength required to resist design loads based on the i strength design methods described in ACI-318-77. ; I f l
1 l i l . I l l l i C. Conclusion ; e Additional loads from high density racks are small compared to other dead loads and the l L hydrostatic loads. ! r e Computed stresses resulting from additional rack , loads when combined with other applicable loads , are within code allowable values. I t I i I i t
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1 i h
Fuel Rack Installation
- 1. Installation sequence same as previous rerack.
l
- 2. Installation equipment same as previous rerack.
- a. Portable 15 ton crane.
- b. Protective cover - with stand drop of new and old spent fuel racks.
- 3. All fuel stored in one pool while modifying other pool.
- 4. No movement of heavy equipment above stored fuel unless pro-tective cover is in place.
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- ~ - - . - -
l
l i Installation Sequence.
- 1. Store spent fuel (441 assemblies) in pool 2.
- 2. Install portable 15 ton crane on the fuel handling bridge crane rails.
- 3. Remove present racks from pool 1 using the portable crane and the main crane.
- 4. Cut off existing anchor bolts (locations with interference).
- 5. Install new racks in pool 1.
- 6. Transfer all spent fuel to pool 1.
- 7. Install protective cover on pool 1.
- 8. Remove existing racks from pool 2.
- 9. Cut off existing anchor bolts (locations with interference).
- 10. Install new racks in pool 2.
- 11. Return spent fuel to pool 2.
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